ML20215D734

Safety Evaluation Re Util 860623 Request That One Startup Test Be Modified & Five Startup Tests Be Eliminated.Mod to Rod Drop Measurement Test & Elimination of Certain Other Startup Tests Acceptable

ML20215D734
Person / Time
Site:	Byron, Braidwood, 05000000
Issue date:	10/01/1986
From:	NRC, Office of Nuclear Reactor Regulation
To:
Shared Package
ML20215D715	List: ML20215D711 ML20215D734
References
NUDOCS 8610140270
Download: ML20215D734 (5)

Text

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SAFETY EVALUATION BYRON STATION UNIT 1 & 2 BRAIDWOOD STATION UNITS 1 & 2 Docket Nos. 50-454/455/456/457 ROD DROP MEASUREMENTS This test sunnary requires measurement of rod drop times at cold no-flow, cold full-flow, hot no-flow, and hot full-flow conditions following core loading. The applicant proposed to modify the test sunnary to indicate that it applies to Byron Unit 1 only, and to add a new sunnary for Byron Unit 2 as well as Braidwood Units 1 & 2 which require measurement of rod drop times at hot, full-flow conditions only. The applicant's justificatien for this change is that the Westinghouse Acceptance Criteria apply to the hot full-flow condition only, and that from previous experience they have found rod drop times at other test conditions fall under the hot, full-flow values. We find this justification bounds the other test conditions, these additional testsare not necessary, and therefore the proposed modification is acceptable.

PSEUD 0 ROD EJECTION The Applicant has proposed to modify the test sunnary to indicate that it applies to Byron Unit 1 only. Verification of core design parameters for -

Byron Unit 2 and Braidwood Units 1 & 2 will be achieved through control rod worth measurements, boron worth measurements, and flux mapping at zero power.

The purpose of this test is to verify calculational models and accident analysis assumptions. These design features have been verified on Byron Unit 1. Reg Guide 1.68, Appendix A, Item 5.e specifically allows the test to be deleted for facilities using calculational models and designs identical to prototype facilities. This change is acceptable.

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FLUX ASYMMETRY EVALUATION The applicant proposed to delete this test from the Startup Test Program for Byron Unit 2 and Braidwood Units 1 & 2. The performance of this test on Byron Unit I has confimed that the core thermal and nuclear parameters are in accordance with predictions. We find thi:: change acceptable.

TURBINE TRIP FROM 25% POWER The applicant proposed to delete this test from the Startup' Test Program for Byron Unit 2 and Braidwood Units 1 & 2. This test is not required since a 100% power full load rejection test will be performed in accordance '

with Reg Guide 1.68, Appendix A. Item 5.n.n. This change is therefore acceptable.

SHUTDOWN FROM OUTSIDE THE CONTROL ROOM The applicant / licensee has proposed to modify the test suninary to indicate that it will be performed on Byron Unit 1 only. The applicant justifies this change on the basis of preoperational tests of the remote shutdown -

l systems, which require the plant to be maintained in the hot standby l

condition for at least 30 minutes, and which provide all necessary design information regarding remote shutdown capability.

Regulatory Guide 1.68.2 Section C states, in part, that the test program should verify that "the nuclear power plant can be safely shutdown from outside the control room." The applicant has provided no alternative test which will demonstrate this capability. In addition, Regulatory Guide 1.68.2 states, in part, that "li,censees... conduct a test program to demon-strate remote shutdown capability for each unit of their plants." This-demonstration is necessary to verify proper operatien of the remote shut-down capability on each unit. Experience at other facilities has demon-stratedthat preoperational and subsystem level tests do not achieve these objectives. This change is, therefore, not acceptable.

LOSS OF OFFSITE POWER f The applicant has proposed to modify the test summary to indicate that it will be performed on Byron Unit 1 only. The applicant justifies this on the basis of the test performed on Byron Unit 1, and the preoperational test program on Byron Unit 2 and Braidwood Units 1 & 2 which verifies that onsite power systems are functional.

Regulatory Guide 1.68 Appendix A Section 5 j.j states that the test program

" demonstrate that the dynamic response of the plant is in accordance with design for a condition of loss of turbine-generator conincident with loss of all sources of offsite power (i.e., Station Blackout)." While the test performed on Byron Unit I demonstrated that the plant design is adequate, each unit must be tested to verify that the hardware performance at the system level is as expected. Experience at other facilities has demonstrated that preoperational and subsystem level tests are not adequate to demonstrate that the dynamic response of each unit is in accordance with design. This change is, therefore, not acceptable..

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Enclosure 2 REQUEST FOR ADDITIONAL. INFORMATION INITIAL. STARTUP PROGRAM, FSAR AMENDMENT 47 I

1. The acceptance criteria in Table 14.2-82 was changed in FSAR Amendment

47. The new criteria disregards the sign of the measured power coefficient verification factor by taking its absolute value. This allows the measured power coefficient to be either positive or negative, {

as long as its magnitude is within 10,5*F/% power of the predicted power j coefficient verification factor. This is not acceptable. i Provide the basis for the new criteria or revert back to the criteria in place prior to Amendment 47,

2. Question 423.47 addresses the primary safety and relief valves and the steam generator safety and relief valves in the first part of the first j sentence. However, reference to the steam generator safety and relief j valves was inadvertently omitted from the portion of the sentence that asked you to demonstrate that the capacity of the valves is consistent with the accident analysis assumptions. Therefore, answer Question j 423.47 as though the words " steam generator safety and relief valves" were placed after " pressurizer power operated relief valves."  !

3. In the test sumary of Table 14.2-89 it now states that "the plant will be tripped by manual trip or by initiation of an automatic trip of the {

i generator breakers." It is not clear how the manual trip will be (

initiated. Modify Table 14.2-85 to provide the necessary clarification.

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